Letter Sequence Response to RAI |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement, Supplement, Supplement, Supplement
Results
Other: L-09-056, Downstream Effects for Recirculation Spray System Pumps and Low Head Safety Injection System Pumps, L-13-176, Generic Safety Issue 191 Resolution Plan, ML061380273, ML080220343, ML081230116, ML082740241, ML090750619, ML090900193, ML091050100, ML091240030
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MONTHYEARL-05-034, Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.2005-03-0404 March 2005 Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. Project stage: Request ML0515302672005-06-0303 June 2005 6/3/05, Beaver Valley, RAI, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors Project stage: RAI ML0520801672005-07-22022 July 2005 Response to Request for Additional Information on Generic Letter 2004-02 Project stage: Response to RAI L-05-123, Response to Request for Additional Information on Generic Letter 2004-022005-07-22022 July 2005 Response to Request for Additional Information on Generic Letter 2004-02 Project stage: Response to RAI L-05-151, August 24, 2005 Extended Power Uprate Meeting Presentation Material2005-09-0101 September 2005 August 24, 2005 Extended Power Uprate Meeting Presentation Material Project stage: Request L-05-140, Response to a Request for Additional Information (RAI Dtd August 2, 2005) in Support of License Amendment Request Nos. 302 and 173, Extended Power Uprate2005-09-0606 September 2005 Response to a Request for Additional Information (RAI Dtd August 2, 2005) in Support of License Amendment Request Nos. 302 and 173, Extended Power Uprate Project stage: Response to RAI ML0603803422006-02-0909 February 2006 Request for Additional Information Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors TAC Nos. MC4665 and MC4666 Project stage: RAI ML0609604422006-04-0303 April 2006 Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML0613802732006-05-18018 May 2006 Request for Scheduler Extension from Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors (TAC No. MC46666) Project stage: Other ML0731005762007-11-0808 November 2007 Notice of Meeting to Discuss the Safety Review Process and Environmental Scoping Process for Beaver Valley Power Station, Units 1 and 2, License Renewal Application Review Project stage: Meeting ML0802203432008-01-14014 January 2008 Letter from George Dudash III, Comment Regarding the Beaver Valley Power Station Unit 1 and 2 License Renewal Project stage: Other ML0805102462008-02-14014 February 2008 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - Request for Extension of Completion Date for Corrective Actions Project stage: Request L-08-054, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - Request for Extension of Completion Date for Corrective Actions2008-02-14014 February 2008 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - Request for Extension of Completion Date for Corrective Actions Project stage: Request L-08-035, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized - Water Reactors2008-02-29029 February 2008 Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized - Water Reactors Project stage: Supplement ML0806605972008-02-29029 February 2008 Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized - Water Reactors Project stage: Supplement ML0812301162008-02-29029 February 2008 Extension Request Approval Letter Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors,. Project stage: Other ML0807301162008-03-21021 March 2008 Summary of Conference Call Between Us Nuclear Regulatory Commission and Firstenergy Nuclear Operating Company, Concerning the Impact of Table 8.0-1 Error on the Beaver Valley Severe Accident Mitigation Alternatives Request for Additional in Project stage: Request ML0807403922008-03-26026 March 2008 Summary of Telephone Conference Between NRC and Firstenergy Nuclear Operating Company, Concerning Clarification of Severe Accident Mitigation Alternatives Request for Additional Information Pertaining to Beaver Valley Units 1 & 2 Project stage: RAI ML0812304992008-06-0303 June 2008 Teleconf Held 4/30/08 Between NRC and Firstenergy Concerning the RAI Pertaining to the Refurbishment Activities at Beaver, Units 1 and 2, LRA Project stage: Request ML0824800452008-08-28028 August 2008 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, Request for Extension of Completion Date for Corrective Actions Project stage: Request L-08-257, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, Request for Extension of Completion Date for Corrective Actions2008-08-28028 August 2008 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, Request for Extension of Completion Date for Corrective Actions Project stage: Request ML0827402412008-09-30030 September 2008 Extension Request Approval Letter Generic Letter 2004--02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Other ML0826001472008-09-30030 September 2008 NUREG-1437 Supp 36, Dfc, Generic Environmental Impact Statement for License Renewal of Nuclear Plants: Regarding Beaver Valley Power Station, Units 1 & 2 (Draft for Comment) Project stage: Draft Other ML0830800942008-10-29029 October 2008 Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Supplement L-08-321, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors2008-10-29029 October 2008 Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Supplement L-09-056, Downstream Effects for Recirculation Spray System Pumps and Low Head Safety Injection System Pumps2009-03-11011 March 2009 Downstream Effects for Recirculation Spray System Pumps and Low Head Safety Injection System Pumps Project stage: Other ML0907506192009-03-11011 March 2009 Downstream Effects for Recirculation Spray System Pumps and Low Head Safety Injection System Pumps Project stage: Other ML0909001932009-03-31031 March 2009 Extension Request Approval Letter Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors, Project stage: Other ML0910501002009-04-21021 April 2009 Correction Letter Extension Request Approval to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Other ML0912501802009-04-30030 April 2009 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - Request for Extension of Completion Date for Additional Corrective Actions Project stage: Request L-09-131, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - Request for Extension of Completion Date for Additional Corrective Actions2009-04-30030 April 2009 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - Request for Extension of Completion Date for Additional Corrective Actions Project stage: Request ML0912400302009-05-0505 May 2009 Extension Request Approval Letter Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Other L-09-152, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2009-06-30030 June 2009 Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Supplement ML1002903182010-02-18018 February 2010 RAI, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: RAI ML1008407562010-03-31031 March 2010 Notice of Teleconference Meeting with Firstenergy Nuclear Operating Company Regarding Mutual Understanding of NRR Staffs Request for Additional Information and to Discuss Generic Letter 2004-02 Project stage: RAI ML1013206652010-05-18018 May 2010 Summary of Category 1 Teleconference with Firstenergy Nuclear Operating Company to Discuss NRC Request for Additional Information Regarding Generic Letter 2004-02 Project stage: RAI L-13-176, Generic Safety Issue 191 Resolution Plan2013-05-16016 May 2013 Generic Safety Issue 191 Resolution Plan Project stage: Other 2008-03-21
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-ENOC Beaver Valley Poer Station FENOCRoute 168 RPO. Box 4 FirstEnergy Nuclear Operating Comnpany Shippingport, PA 15077-0004 James IL. Lash 724-682-7773 Director, Site Operations July 22, 2005 L-05-123 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Beaver Valley Power Station, Unit Nos. 1 and 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Response to Request for Additional Information on Generic Letter 2004-02 (TAC Nos. MC4665 and MC4666)
By letter dated March 4, 2005, the FirstEnergy Nuclear Operating Company (FENOC) submitted its initial response to Generic Letter 2004-02 for Beaver Valley Power Station Unit Nos. I and 2.
By letter dated June 3, 2005, the NRC requested additional information regarding the FENOC response to Generic Letter 2004-02. The FENOC responses to this request are provided in Attachment 1. Attachment 2 provides a list of regulatory commitments made in this submittal.
Should you have any questions or require additional information, please contact Mr. Henry L. Hegrat, Supervisor - Licensing, at (330) 315-6944.
I declare under penalty of perjury that the foregoing is true and correct. Executed on July _2L~, 2005.
Sincerely, es H. Lash Attachments
- 1. FENOC Response to Request for Additional Information
- 2. Commitment List
Beaver Valley Power Station, Unit Nos. 1 and 2 Response to RAI on Generic Letter 2004-02 L-05-123 Page 2
References:
- 1. Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors," dated September 13, 2004
- 2. Response (L-05-034) to Generic Letter 2004-02 for Beaver Valley Power Station Unit Nos. 1 and 2, dated March 4, 2005
- 3. NRC Request for Additional Information Related to Generic Letter 2004-02, dated June 3, 2005 c:
Mr. T. G. Colburn, NRR Senior Project Manager Mr. P. C. Cataldo, NRC Senior Resident Inspector Mr. S. J. Collins, NRC Region I Administrator
ATrACHMENT 1 to L-05-123 FENOC Response to Request for Additional Information Regarding Generic Letter 2004-02 Beaver Valley Power Station REQUEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER 2004-02 "POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY SUMP RECIRCULATION AT PRESSURIZED-WATER REACTORS" FIRSTENERGY NUCLEAR OPERATING COMPANY BEAVER VALLEY POWER STATION. UNITS 1 AND 2 DOCKET NOS. 50-334 AND 50-412 By letter dated March 4, 2005, FirstEnergy Nuclear Operating Company (the licensee) provided the 90-day response to U. S. Nuclear Regulatory Commission (NRC) Generic Letter (GL) 2004-02 for Beaver Valley Power Station, Units 1 and 2. The GL requested that addressees perform an evaluation of the emergency core cooling system and containment spray system recirculation functions in light of the information provided in the GL and, if appropriate, take additional actions to ensure system function.
Additionally, addressees were requested to submit to the NRC the information specified in the GL. The staff has completed its preliminary review of your response and has determined it needs the following additional information to complete our review:
As a result of the review of the 90-day responses for all licensees and recent discussions with industry, the staff is concerned that some licensees may be delaying the evaluation of chemical and downstream effects until after the September 1, 2005, due date for the next response to the GL. This would result in an incomplete response and is not in accordance with the schedule in the GL. Your 90-day response indicated that your analysis will be completed by September 1,2005, but did not discuss the evaluation of chemical and downstream effects. Although the GL did not specifically request that the evaluation of chemical and downstream effects be discussed in the 90-day response, please discuss your plans and schedule for evaluating chemical and downstream effects and verify whether your September 1, 2005, response will include an evaluation of these effects.
Response
The NRC and the nuclear industry are examining the impact of chemical interactions on the long-term head loss correlation presently used in containment sump analyses. A test program is currently underway at the Los Alamos National Laboratory (LANL). While no finalized results have yet been published, initial information shows that there are, in fact, long-term chemical effects on the debris bed head loss. The testing is attempting to develop a correlation to permit quantification of these effects. At this time, it is not feasible to quantify the impact of the chemical effects.
Since a quantitative assessment is not possible at this time, the September 1, 2005 response for Beaver Valley Power Station will include a qualitative assessment of chemical effects.
Additionally, following completion of the LANL testing program, an evaluation of the chemical effects on the debris bed head loss will be performed.
Page 1 of 2 to L-05-123 FENOC is doing a downstream effects review in accordance with the guidance of Regulatory Guide 1.82, Rev. 3, "Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident", and of Section 7.3 of NEI 04-07, "Pressurized Water Reactor Sump Performance Evaluation Methodology". The Safety Evaluation Report on NEI 04-07 raised additional issues to consider when doing downstream effects analyses. The Westinghouse Owners Group developed WCAP-16406, "Evaluation of Downstream Sump Debris Effects in Support of GSI-191" to describe methods to be used in addressing the downstream effects issues. The WCAP was just published in June 2005. FENOC will do additional evaluations using the guidance provided in the WCAP.
However, a vendor with the expertise and availability to do these evaluations has not yet been identified, so the schedule for the evaluations has not yet been defined. The plan for conducting evaluations of the downstream effects of containment sump debris will be discussed in the September 1, 2005 response to Generic Letter 2004-02.
Page 2 of 2
ATTACHMENT 2 to L-05-123 Comniitment List The following list identifies those actions committed to by FENOC for Beaver Valley Power Station (BVPS) Unit Nos. 1 and 2 in this document. Any other actions discussed in the submittal represent intended or planned actions by FENOC. They are described only as information and are not regulatory commitments. Please notify Mr. Henry L.
Hegrat, Supervisor - Licensing at 330-315-6944 of any questions regarding this document or associated regulatory commitments.
Commitment The September 1, 2005 response to Generic Letter 2004-02 will include a qualitative assessment of chemical effects Perform an evaluation of the chemical effects on the debris bed head loss.
The plan for conducting evaluations of the downstream effects of containment sump debris will be discussed in the September 1, 2005 response to Generic Letter 2004-02.
Due Date September 1, 2005 Following completion of the LANL testing program September 1, 2005 Page 1 of 1